ML21278A116

2 to Updated Final Safety Analysis Report, Chapter 4, Appendix 4A Figures

ML21278A116
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Site:	Calvert Cliffs
Issue date:	09/07/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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Text

Rev. 18 A

REACTOR COOLANT PUMP FLOW TEST INSTRUMENTATION

~RSCHEL TYPE 24" x 17 1/2'~ VENTURI

.-~~~~~~~~~~

BARTON MOD 200..._ _

No. I, 0-20 psi t 0.5% F.S.

BARTON MOD 2 No.~ 0-20 psi

- 0.5% F.S.

BARTON MOD 200 No.4, 0-15 psi

+/-0.5% F.S.

BARTON MOD 200 No.33898, 0-15 psi..._ _

+/-0.5% F.S.

ROYLYN No. 5 0-3000 psi

• O. 25o/o...

- BARTON MOD 227 1o----i 0-150 psid i: 0.5% F.S.

CROSBY No. 4 0-3000 psi t 0.5% F.S.

BALTIMORE GAS & ELECTRIC CO.

Calvert Cliffs Nuclear Power Plant REACTOR COOLANT PUMP FLOW TEST INSTRUMENTATION Figure A Rev.18

Rev. 18 B

ERROR IN ESTABLISHMENT OF FLOW TRUE PUMP CASE AP MEASURED TEST LOOP AP

+ 0.5% FS =

+ 0. 75 PSI AP* 85 PSI AP.. 85

+ 0. 75 PSI AP max 85. 75 PSI

6. p INDIVIDUAL PUMP

.__._!o1oo1~ CURVE I

I I

I I

I I

I I

I

'f \\

92 500

.)

94, 940

~

I

!::. p = 85 - (Q.005) 85 PSI TRUE TEST LOOP FLOW" TRUE.

REACTOR COOLANT SYSTEM FLOW VENTURI t::.P

+ 1%0F THEORETICAL MEASURED VENTURI AP

!: 2.5%

OF READING t

. CALCULATED TEST LOOP FLOW ALLOWANCE FOR PUMP CASE AREA VARIATION 840 GPM APPARENT REACTOR COOLANT SYSTEM FLOW, WORST CASE ERRORS MEASURED PUMP A P IN REACTOR COOLANT SYSTEM

!: 0.5% OF READING t::.Pmin 84.57 PSI'------~

Q = 92,500 ~PM t::,. Pc( 8. 64 x 109

+ (. 02518. 64 xl09 A Pm~x B. 86 x 109 Q=./4E T

Q.)s.86x109 qr.ax 94, 100 GPM Offiax94, 940 GPM 0niax = 96,100 GPM Figure B BALTIMORE GAS & ELECTRIC CO.

Calvert Cliffs Nuclear Power Plant ERROR IN ESTABLISHMENT OF FLOW Rev. 18